ML20238D019
| ML20238D019 | |
| Person / Time | |
|---|---|
| Issue date: | 08/14/1987 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML20238C988 | List: |
| References | |
| RTR-REGGD-1.100, TASK-EE-108-5, TASK-RE REGGD-01.100, REGGD-1.100, NUDOCS 8709100511 | |
| Download: ML20238D019 (4) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION August 1987 3'
't, OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 3
i Task EE 108-5 DRAFT REGULATORY GUIDE o
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Contact:
S. K. Aggarwal (301) 443-7840 PROPOSED REVISION 2 TO REGULATORY GUIDE 1.100 SEISMIC QUALIFICATION OF ELECTRIC AND MECHANICAL EQUIPMENT FOR NUCLEAR POWER PLANTS
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hk A.
INTRODUCTION 44 f
The Commission's regulations in 10 CFR Part 50, "D6mesB9 Licensing of Production and Utilization Facilities," require that [ ptfi tructures, systems, a
0 andcomponentsinanuclearpowerplantbedesignedgto
' stand the effects of naturalphenomenasuchasearthquakes,andthatpesi^g[y1$bntrolmeasuressuch
,,w astestingbeusedtochecktheadequacyofdes1%
is general requirement iscontainedinAppendixA,"GeneralDesignChtei for Nuclear Power Plants,"
as toPart50;inCriterionIII,"DesignCongql"gn Criterion XVII, " Quality AssuranceRecords,"ofAppendixB," Qual,ithssuranceCriteriaforNuclearPower PlantsandfuelReprocessingPlants,"ttbirt$0;andinAppendixA," Seismic 1
iS and Geologic Siting Criteria for N a g er Plants," to Part 100, " Reactor Site Criteria."
4 InAppendixAto10CFRPartk00 $ectionVI,"ApplicationtoEngineering Design," requires that the nuclear power plant be designed so that, if the safe shutdown earthquake occurs, certain structures, systems, and components will m
remain functional.
Thesefsafety-related structures, systems, and components are those necessary to e% y mnsure (1) the integrity of the reactor coolant pressure en my boundary,(2)thecapahi1{$111t ty to shut down the reactor and maintain it in a safe condition, or (3) thk y to prevent or mitigate the consequences of accidents that coul@ result in offsite exposures comparable to the Part 100 ya guidelines.
InApp'egdixAtoPart100,SectionVI(a)(2)requiresthat EO O'" S.INfeNi$ fiA'EI! Ne!.'It C Ut $ $I*eEEoE"INl N.N*rl*i5InE' J'nN*r$ l net an officist hRC staff position.
Public comments are bein solicited on the draf t guide (including any implementation schedule) and its a sso=
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esamined at the NRC Public Document Room, 1717 H Street NW.
Washington, DC.
Comments will be most helpful er received ey October 30, 1987.
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U.S. Nuclea r Regulatory Commission, Washington, DC 20555. Attention; Director, Division of Information Suppert Services.
9709100511 870814 PDR REQ 9D 01.100 R PDR
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structures, systems, and com;:onents of the nuclear pxr plant necewary for continued operation wi;.nout undue risk to the health and safety of the public be designed to remain fonctional and within. applicable stress and deformation limits when subjected to the effects of the vibratory motion of an opert. ting basis earthquake in conainatirrt with normal Anerating loads.
The engineering l
aethod used to ensure that tue required safety functiona are maintained during and after the vibrttory ground motion associated with the safe shutdown earthquake or the operating basis earthquake must involve the use of either a suitable dynamic analysis or a suitabie qualification tesi, to demonstrate that structures, systems, ar.d components'can withstand the seismic and other con-l current loads.
l This regulatory guide describes a method hcceptable to the NRC staff for comp'ying with NRC's regulations with respect to seis:nic qualification of electric and mechanical equipment.
Any information collection activities mentioned in this draf t. reGulatery guide are contained as requirements in 10 CFR Parts 50 or 100, which provine the tr:gulatory basis for this guide.
The information collection requiro.tacnts in 10 CFR Parts 50 and 100 have been cleared under OMB Clearanco Nos. 31F0-0011 and 3.150-0093, respectively.
B.
D_ISCUSSION IEEE Std 344-1987, Recommended Practice for Seismic Qualification of Class 1E Equipment for Muclecr Power Generating Stations,"* was prepared by Working G' oup 2.5 (Seismic Qualification) of Subcommittee 2 (Equipment Quali-fication) af the InstittLe o? Elettrical and Electronics Engineers (IEEE)
Nuclear P< er Engineering Com.'nittee, and wn subsequently approved by the IEEE Stand rds Board on June 13, 1987.
The IEEE Standard i:cludes principles, procedures, and methods of seismic qualification that, when satisfied, will confirm the adequacy of the equipment-design for the performance of safety functions before, during, and af ter the
- Copies may be obtained from the Institute of Electrical aid Electronics Engineers, IEEE Service Center 44b Hoes Iane, P.O. Box 1331, Piscataway, NJ 08655.
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titre the safety-related equipment is subjected to high stresses resulting from design Dasis events.
For this guide, the design basis events are the loadings imposed by seismic events:
the operating basis earthquake (0BE) and the safe shutdown earthquake (3SE).
It is also necessary to combine other dynamic or vibratory loads as part of seismic qualification.
It is recognized that hydrodynamic loads have their primary energy content in a frequency range greater than that of seismic vibrations; however, they are a part of the in-plant equipment aging process, along with other nonseismic vibration ioads, and therefore should be considered in seismic testing.
Revision 1 of this guide was issued in August 1977.
Since then, several new technical issues have c-isen, such as treatment of hydrodynamic loads, the limits of generic testing, the treatment of rattling, methods of qualifying line-mounted devices, and the use of actual seismic experience data bases to qualify identical or similar equipment.
These issues are covered by IEEE Std 344-1987, which reflects the state-of-the art technology.
Further, the NRC has extended the application of this standard to the qualification of mechanical equipment.
This regulatory guide covers two categories of equipment:
(1) safety-related electric (Class 1E) equipment and safety-related mechanical equipment, and (2) equipment whose failure can prevent the satisfactory accomplishment of safety functions.
Examples of mechanical equipment and equipment supports within the scope of this guide are valves, valve operators, pumps, compressors, chillers, air handlers, fans, blowers, pipe supports, snubbers, restraints, hangers, fuel rod assemblies, and control rod drive mechanisms.
IEEE Std 344-1987 references other standards that contain valuable informa-tion.
Those referenced standards not endorsed by a regulatory guide or incor-porated into the regulations, if used, are to be used in a manner consistent with current regulations.
C.
REGULATORY POSITION The procedures described by IEEE Std 344-1987, " Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations," are acceptable to the NRC staff for satisfying the Commission's regulations pertaining to seismic qualification of electric and.nechanical equipment subject to the following:
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l 1.
For mechanical equipment, thermal distortion effects on operability should be considered, and loads imposed by the attached piping should also be accounted for.
If dynamic testing of a pump or a valve assembly is impracticable, static testing of the assembly is acceptable provided that (1) the end loadings are applied and are equal to or greater than postulated event loads, (2) all dynamic amplification effects are accounted for, (3) the component is in the operating mode during and after the application of loads, and (4) an adequate analysis is made to show the validity of the static application of loads.
2.
Section 9 of IEEE Std 344-1987 recognizes the use of experience data as a method for seismic qualification.
This method of qualification should be appropriately justified so it can be evaluated by the NRC staff on a case-by-case basis.
D.
IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described herein will be used in the evaluation of seismic qualification of electric and mechanical equipment for nuclear power plants as follows:
1.
Plants for which the construction permit is issued after the issue date of the final guice, 2.
Plants for which the operating license application is docketed for 6 months or more after the issue date of the final guide, 3.
Plants for which the applicant or licensee voluntarily commits to the provisions of this guide.
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